ML070300021
| ML070300021 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/09/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLIV |
| To: | |
| Lyon C Fred, NRR/DORL/LPL4, 301-415-2296 | |
| Shared Package | |
| ML070300011 | List: |
| References | |
| TAC MD1225 | |
| Download: ML070300021 (3) | |
Text
(3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
(6)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to store byproduct, source and special nuclear materials not intended for use at Columbia Generating Station. The materials shall be no more than 9 sealed neutron radiation sources designed for insertion into pressurized water reactors and no more than 40 sealed beta radiation sources designed for use in area radiation monitors. The total inventory shall not exceed 24 microcuries of strontium-90, 20 microcuries of uranium-235, 30 curies of plutonium-238, and 3 curies of americium-241.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3486 megawatts thermal). Items in shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 201 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- a.
For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in'the Technical Specifications as revised in Amendment No. 149.
Amendment No. -2e, 201
Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and In accordance leakage rate testing except for primary with the containment air lock testing, in Primary accordance with the Primary Containment Containment Leakage Rate Testing Program.
Leakage Rate Testing Program SR 3.6.1.1.2 Verify drywell to suppression chamber bypass leakage is < 10% of the acceptable A/Ji-design value of 0.050 ft 2 at an initial differential pressure of > 1.5 psid.
120 months AND 48 months following a test with bypass leakage greater than the bypass leakage limit AND 24 months following two consecutive tests with bypass leakage greater than the bypass leakage limit until two consecutive tests are less than or equal to the bypass leakage limit (continued)
Columbia Generating Station 3.6.1.1-2 Amendment No.
149,169, 201
Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.6.1.1.3
NOTE---------------
Performance of SR 3.6.1.1.2 satisfies this surveillance.
Verify individual drywell to suppression chamber vacuum relief valve bypass pathway leakage is
< 1.2% of the acceptable A/J-design value of 0.050 ft 2 at an initial differential pressure of
> 1.5 psid.
24 months I.
SR 3.6.1.1.4 NOTE----------------
Performance of SR 3.6.1.1.2 satisfies this surveillance.
Verify total drywell to suppression chamber vacuum relief valve bypass leakage is
< 3.0% of the acceptable A/VK design value of 0.050 ftW at an initial differential pressure of > 1.5 psid.
24 months Columbia Generating Station 3.6.1.1-3 Amendment No. 201